Download or read book Alloy Dispersion Fuel Elements written by J. Paul Pemsler and published by . This book was released on 1959 with total page 30 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Dispersion Fuel Elements written by Abe Noel Holden and published by . This book was released on 1967 with total page 276 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Dispersion Fuels for Advanced Organic Moderated Reactor written by J. Kroehler and published by . This book was released on 1960 with total page 48 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Irradiation Behavior of Dispersion Fuels written by D. W. White (Jr.) and published by . This book was released on 1957 with total page 62 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Dispersions of Uranium Carbides in Aluminum Plate type Research Reactor Fuel Elements written by W. C. Thurber and published by . This book was released on 1959 with total page 58 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Structural Materials for Generation IV Nuclear Reactors written by Pascal Yvon and published by Woodhead Publishing. This book was released on 2016-08-27 with total page 686 pages. Available in PDF, EPUB and Kindle. Book excerpt: Operating at a high level of fuel efficiency, safety, proliferation-resistance, sustainability and cost, generation IV nuclear reactors promise enhanced features to an energy resource which is already seen as an outstanding source of reliable base load power. The performance and reliability of materials when subjected to the higher neutron doses and extremely corrosive higher temperature environments that will be found in generation IV nuclear reactors are essential areas of study, as key considerations for the successful development of generation IV reactors are suitable structural materials for both in-core and out-of-core applications. Structural Materials for Generation IV Nuclear Reactors explores the current state-of-the art in these areas. Part One reviews the materials, requirements and challenges in generation IV systems. Part Two presents the core materials with chapters on irradiation resistant austenitic steels, ODS/FM steels and refractory metals amongst others. Part Three looks at out-of-core materials. Structural Materials for Generation IV Nuclear Reactors is an essential reference text for professional scientists, engineers and postgraduate researchers involved in the development of generation IV nuclear reactors. Introduces the higher neutron doses and extremely corrosive higher temperature environments that will be found in generation IV nuclear reactors and implications for structural materials Contains chapters on the key core and out-of-core materials, from steels to advanced micro-laminates Written by an expert in that particular area

Download or read book Properties of Uranium Dioxide stainless Steel Dispersion Fuel Plates written by Stan J. Paprocki and published by . This book was released on 1959 with total page 32 pages. Available in PDF, EPUB and Kindle. Book excerpt: The physical and mechanical properties of GCRE-type fuel elements were determined from room temperature to 1650 deg F. The fuel elements were prepared by cladding Type 318 stainless steel sheet to a core containing 15 to 35 wt.% UO/ sub 2/ in either prealloyed Type 318 stainless steel or elemental iron-18 wt.% chromium-14 wt. % nickel-2.5 wt. % molybdenum. The tensile strength in the direction perpendicular to the rolling plane decreased from 24,600 psi at room temperature to 9,200 psi at 1650 deg F for the reference fuel plate, whose core contained 25 wt.% UO2 in the elemental alloy. The tensile strength in the longitudinal direction for this fuel element ranged from 54,800 psi at room temperature to 14,200 psi at 1650 deg F, with elongation in 2 in. ranging from 8 to 13 per cent. The extrapolated stress for 1000hr rupture life at 1650 deg F was 1800 psi, and a 1.4T bend was withstood without cracking. The mean linear thermal coefficient of expansion was 11.0 x 10−6 per deg F for the range 68 to 1700 deg F. (auth).

Download or read book Material Properties of Unirradiated Uranium Molybdenum U Mo Fuel for Research Reactors written by International Atomic Energy Agency and published by . This book was released on 2020-10-12 with total page 144 pages. Available in PDF, EPUB and Kindle. Book excerpt: This publication presents the material properties of all unirradiated Uranium-Molybdenum (U-Mo) fuel constituents that are essential for fuel designers and reactor operators to evaluate the fuel's performance and safety for research reactors. Many significant advances in the understanding and development of low enriched uranium U-Mo fuels have been made since 2004, stimulated by the need to understand irradiation behavior and early fuel failures during testing. The publication presents a comprehensive overview of mechanical and physical property data from U-Mo fuel research

Download or read book High Density Dispersion Fuel written by and published by . This book was released on 1996 with total page 7 pages. Available in PDF, EPUB and Kindle. Book excerpt: A fuel development campaign that results in an aluminum plate-type fuel of unlimited LEU burnup capability with an uranium loading of 9 grams per cm3 of meat should be considered an unqualified success. The current worldwide approved and accepted highest loading is 4.8 g cm−3 with U3Si2 as fuel. High-density uranium compounds offer no real density advantage over U3Si2 and have less desirable fabrication and performance characteristics as well. Of the higher-density compounds, U3Si has approximately a 30% higher uranium density but the density of the U6X compounds would yield the factor 1.5 needed to achieve 9 g cm−3 uranium loading. Unfortunately, irradiation tests proved these peritectic compounds have poor swelling behavior. It is for this reason that the authors are turning to uranium alloys. The reason pure uranium was not seriously considered as a dispersion fuel is mainly due to its high rate of growth and swelling at low temperatures. This problem was solved at least for relatively low burnup application in non-dispersion fuel elements with small additions of Si, Fe, and Al. This so called adjusted uranium has nearly the same density as pure [alpha]-uranium and it seems prudent to reconsider this alloy as a dispersant. Further modifications of uranium metal to achieve higher burnup swelling stability involve stabilization of the cubic [gamma] phase at low temperatures where normally [alpha] phase exists. Several low neutron capture cross section elements such as Zr, Nb, Ti and Mo accomplish this in various degrees. The challenge is to produce a suitable form of fuel powder and develop a plate fabrication procedure, as well as obtain high burnup capability through irradiation testing.

Download or read book Nuclear Regulatory Commission Issuances written by U.S. Nuclear Regulatory Commission and published by . This book was released on 1979 with total page 950 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Uranium Aluminum Alloy Powders for Use as Nuclear Reactor Fuels written by and published by . This book was released on 1963 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The trend toward higher fuel densities in reactor cores is noted. The use of powdered U -Al intermetallic compounds would provide the desired high fuel densities with a minimum of fabrication troubles, and burnable poisons can be added. The properties of U and U--Al compounds are described; UAl/sub 2/ and UAl/ sub 2/ appear to be the most attractive fissile dispersants in dispersion-type fuel elements. Plates of Al- UAl/sub 3/ were fabricated and irradiated along with Al - U/sub 3/O/sub 8/ plates. The results showed that the s. (D.L.C.).

Download or read book Development of Uranium Nitride stainless Steel Dispersion Fuel Elements written by Stan J. Paprocki and published by . This book was released on 1959 with total page 28 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Report on Civilian Reactor Fuel Elements by the Civilian Reactor Fuel Element Review Group written by M. J. Whitman and published by . This book was released on 1959 with total page 204 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Fabrication of UO2 stainless Steel Dispersion Fuel for Borax v Nuclear Superheat written by W. C. Kramer and published by . This book was released on 1963 with total page 82 pages. Available in PDF, EPUB and Kindle. Book excerpt: The superheat section of the Fifth Boiling Reactor Experiment (BORAX-V) is fueled with enriched uranium (93 wt.% U-235) in the form of uranium dioxide in a matrix of stainless steel. Stainless steel-clad plates containing the fuel were fabricated by the Atomics International Division of North American Aviation.

Download or read book Comprehensive Nuclear Materials written by Todd R Allen and published by Elsevier. This book was released on 2011-05-12 with total page 3552 pages. Available in PDF, EPUB and Kindle. Book excerpt: Comprehensive Nuclear Materials, Five Volume Set discusses the major classes of materials suitable for usage in nuclear fission, fusion reactors and high power accelerators, and for diverse functions in fuels, cladding, moderator and control materials, structural, functional, and waste materials. The work addresses the full panorama of contemporary international research in nuclear materials, from Actinides to Zirconium alloys, from the worlds' leading scientists and engineers. Critically reviews the major classes and functions of materials, supporting the selection, assessment, validation and engineering of materials in extreme nuclear environment Fully integrated with F-elements.net, a proprietary database containing useful cross-referenced property data on the lanthanides and actinides Details contemporary developments in numerical simulation, modelling, experimentation, and computational analysis, for effective implementation in labs and plants

Download or read book Ceramic Fuel Elements written by Robert B. Holden and published by . This book was released on 1966 with total page 260 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Reactor Core Materials written by and published by . This book was released on 1958 with total page 466 pages. Available in PDF, EPUB and Kindle. Book excerpt: